An Am/Be neutron source, installed recently at the Rajshahi University, is described. Neutron flux mapping was done using the nuclear reactions (197)Au(n,gamma)(198)Au, (113)In(n,gamma)(114m)In, (115)In(n,n'gamma)(115m)In and (58)Ni(n,p)(58)Co. An approximate validation of the neutron spectral shape was done using five neutron threshold detectors and the iterative unfolding code SULSA. Integral cross sections of the reactions (54)Fe(n,p)(54)Mn, (59)Co(n,p)(59)Fe and (92)Mo(n,p)(92m)Nb were measured with fast neutrons (E(n)>1.5MeV) and compared with data calculated using the neutron spectral distribution and the excitation function of each reaction given in data libraries: an agreement within +/-6% was found.
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http://dx.doi.org/10.1016/j.apradiso.2010.02.006 | DOI Listing |
Sci Rep
October 2024
Department of Energy Engineering, Sharif University of Technology, Azadi Ave., P.O. Box: 11115-1639, Tehran, Iran.
The current study aims to introduce a new polymeric composite consisting of epoxy resin as the matrix and gadolinium oxide (GdO) as the neutron adsorption ingredient. The shielding performance of the composite was assessed by neutron attenuation experiments with an Am-Be source and polyethylene moderator. The results of these experiments showed an appreciable agreement with the Monte Carlo simulations.
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December 2024
Universidade Federal do Rio de Janeiro, Programa de Engenharia Nuclear (UFRJ/PEN), Avenida Horácio de Macedo, 2030, Bloco G, sala 206, 21941-914, Cidade Universitária, RJ, Brazil.
This study presents an application of an Artificial Neural Network (ANN) to detect fluids in an annular flow regime using Prompt-Gamma Neutron Activation Analysis (PGNAA). The ANN was trained using gamma-ray spectra resulting from neutron interactions with chemical elements found in fluids typical of multiphase flow in oil exploration. These spectra were generated through mathematical simulation using the MCNP6 Monte Carlo computer code to model nuclear particle transport.
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December 2023
National Institute of Nuclear Physics (INFN), 73100 Lecce, Italy.
The shortage of 3He, a crucial element widely used as a neutron converter in neutron detection applications, has sparked significant research efforts aimed at finding alternative materials, developing appropriate deposition methods, and exploring new detector architectures. This issue has required the exploration of novel approaches to address the challenges faced in neutron detection. Among the available conversion materials, 10B has emerged as one of the most promising choices due to its high neutron-capture cross-section and relatively high Q value.
View Article and Find Full Text PDFAppl Radiat Isot
November 2023
Nuclear Power Institute of China, Chengdu, 610000, China.
Appl Radiat Isot
October 2023
Department of Nuclear Safety Engineering, Faculty of Science and Engineering, Tokyo City University, 1-28-1, Tamazutsumi, Setagaya-ku, Tokyo 158-8557, Japan. Electronic address:
Boron neutron capture therapy (BNCT) is a promising cancer treatment that uses energetic ions released from B(n, α)Li reactions. Accurate assessment of neutron energy spectra is important for simulation-based evaluation of neutron doses during BNCT. In this study, a proof-of-concept study was conducted for a neutron spectrometry technique that involves the use of a water phantom, which is commonly used for quality assurance in BNCT, as a moderator.
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